CN109545401A - A kind of lead base fast reactor out-pile passive residual heat removal system - Google Patents

A kind of lead base fast reactor out-pile passive residual heat removal system Download PDF

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Publication number
CN109545401A
CN109545401A CN201811557811.6A CN201811557811A CN109545401A CN 109545401 A CN109545401 A CN 109545401A CN 201811557811 A CN201811557811 A CN 201811557811A CN 109545401 A CN109545401 A CN 109545401A
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CN
China
Prior art keywords
cooling water
pipeline
heat
transfer pipe
increase
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN201811557811.6A
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Chinese (zh)
Inventor
南金秋
周川江
谭璞
张立德
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
Lingdong Nuclear Power Co Ltd
China Nuclear Power Institute Co Ltd
Original Assignee
China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
Lingdong Nuclear Power Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by China General Nuclear Power Corp, China Nuclear Power Technology Research Institute Co Ltd, CGN Power Co Ltd, Lingdong Nuclear Power Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN201811557811.6A priority Critical patent/CN109545401A/en
Publication of CN109545401A publication Critical patent/CN109545401A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

The present invention provides a kind of lead base fast reactor out-pile passive residual heat removal system comprising: cooling water tank, jet chimney, cooling water pipeline, heat-transfer pipe equipped with cooling water;The first end and cooling water tank of cooling water pipeline are connected, and the second end of cooling water pipeline and the first end of heat-transfer pipe are connected;The first end and cooling water tank of jet chimney are connected, and the second end of jet chimney and the second end of heat-transfer pipe are connected;It is provided with steam isolating on jet chimney, cooling water isolation valve is provided on cooling water pipeline;Heat-transfer pipe includes increase in pipeline and the decline pipeline connecting with increase in pipeline one end, is provided with insulating layer between increase in pipeline and decline pipeline;Heat-transfer pipe be arranged in reactor containment vessel, and the increase in pipeline of heat-transfer pipe close to reactor vessel, heat-transfer pipe decline pipeline far from reactor vessel.The advantages that system provided by the invention has heat extraction effect good, and quantity is few and without large scale equipment, easy for installation, easy to maintenance, advantageously reduces reactor vessel inner space.

Description

A kind of lead base fast reactor out-pile passive residual heat removal system
Technical field
The present invention relates to technical field of nuclear power more particularly to a kind of lead base fast reactor out-pile passive residual heat removal system.
Background technique
Lead base fast reactor belongs to forth generation nuclear reactor, is a kind of advanced fast reactor for being able to achieve closure fuel recycle, generally adopts With pool or half pool structure, coolant is lead or lead bismuth alloy, have good neutronics performance, thermohydraulics performance and Inherent safety features.Compared to other forth generation heap-type, such as: sodium-cooled fast reactor (Sodium Cooled Fast Reactor System, SFR), it is extraordinary high temperature gas cooled reactor (Very High Temperature Gas-cooled Reactor, VHTR), super Critical water-water reactor (Supercritical Water Reactor, SCWR), molten salt reactor (Molten Salt Reactor, MSR), gas Cold fast reactor (Gas-cooled Fast Reactor, GFR) has preferable technology maturation, takes in safety and economy Relatively good balance is obtained, is most possible one of the four generation heaps for realizing Industrial demonstration.
Engineered safety system one of of the residual heat removal system as reactor, its design and research, to raising reactor Inherent safety have great importance.Lead base fast reactor uses independent passive residual heat removal system.In recent years, passive peace System-wide research and development is rapid, is widely applied in the design of the third generation and forth generation reactor.Passive peace System-wide advantage has: being worked using inherent characteristics such as medium autologous density difference and gravity, what the system that improves was run can By property;Reduce the thrashing because of caused by power failure;Reduce core melt probability.
A kind of accident afterheat exhausting system of pool type natrium cold fast reactor of China Atomic Energy Science Research Institute's disclosure of the invention uses Passive three circuits design.It is connected in series by independent heat exchanger and air heat exchanger, wherein under independent heat exchanger Portion is immersed in the sodium pond of reactor core, is connected outside air heat exchanger and is pulled out wind and smoke chimney, and system passes through independent heat exchanger for primary Ioops sodium Heat is transmitted to secondary circuit, and the high and low temperature sodium in secondary circuit carries out heat exchange, will finally by the air heat exchanger in three circuits Heat is discharged in atmosphere, and the mode that three circuits of the system are all made of Natural Circulation is run.
European Union Lead cooled fast breeder reactor ALFRED (Advanced Lead Fast Reactor European Demonstrator) The setting of emergency residual heat removal system in steam generator secondary side, designed using passive three circuit, capital equipment has: condensation Device, cooling water tank and corresponding pipeline, valve.Under accident conditions, the main water supply of steam generator and main steam pipe by every From emergency residual heat removal system puts into operation, and secondary circuit water enters steam generator, is heated by primary Ioops lead and generates steam, and steam is logical The condenser that Natural Circulation enters emergency residual heat removal system is crossed, condenser is using the cooling water tank in three circuits as water source, by steam It is condensed into water, condensed water returns to steam generator by gravity, generates steam again, forms circulation, finally arranges reactor waste Toward hot trap --- the cooling water in water tank.
The said goods structure or technology have the drawback that
1. more than pool type sodium cooled fast reactor accident afterheat exhausting system and the passive emergency of European Union's Lead cooled fast breeder reactor ALFRED secondary side The circuit of hot discharge system is more, and thermal resistance is big, and heat extraction effect is poor.
2. the sodium that reactor core is immersed in the lower part of the independent heat exchanger of pool type sodium cooled fast reactor accident afterheat exhausting system Chi Zhong occupies reactor space, is unfavorable for the arrangement of other equipment in reactor, and it is difficult to install in sodium pond, does not allow It is fixed easily.
3. needing to place in the cooling water tank of the passive emergency residual heat removal system of European Union's Lead cooled fast breeder reactor ALFRED secondary side Condenser, size is larger, is unfavorable for space layout, and maintenance difficult.
4. the passive emergency residual heat removal system of European Union's Lead cooled fast breeder reactor ALFRED secondary side is connect with steam generator, and two times Road water at low temperature can cause thermal shock to it, reduce the service life, or even cause deterioration of the equipment failure to cause the accident.
Summary of the invention
In order to solve the above technical problems, the present invention provides a kind of lead base fast reactor out-pile passive residual heat removal system, have Heat extraction effect is good, and quantity is few and without large scale equipment, easy for installation, easy to maintenance, advantageously reduces reactor vessel inner space The advantages that.
A kind of lead base fast reactor out-pile passive residual heat removal system provided by the invention, comprising: the cooling equipped with cooling water Water tank, jet chimney, cooling water pipeline, heat-transfer pipe, steam isolating, cooling water isolation valve;
Wherein, the first end of the first end of the cooling water pipeline and cooling water tank connection and the cooling water pipeline Below cooling water level, the first end of the second end of the cooling water pipeline and the heat-transfer pipe is connected;
The first end of the jet chimney and the cooling water tank are connected, the second end of the jet chimney and the heat transfer The second end of pipe is connected;
Side on the jet chimney close to the cooling water tank is provided with the steam isolating, the cooling water pipe Side on road close to the cooling water tank is provided with the cooling water isolation valve;
The heat-transfer pipe is U-shaped heat-transfer pipe, and the heat-transfer pipe includes increase in pipeline and connects with described increase in pipeline one end The decline pipeline connect is provided with insulating layer between the increase in pipeline and the decline pipeline;
The heat-transfer pipe is arranged in reactor containment vessel, and the increase in pipeline of the heat-transfer pipe is attached to outside reactor vessel Portion, the increase in pipeline are used for the heat of absorbing reaction heap primary Ioops.
Preferably, the heat-transfer pipe further comprises more increase in pipeline and corresponds with the more increase in pipeline More decline pipelines of connection;
The more decline pipelines gather the as the first end of the heat-transfer pipe and the cooling water pipeline after main pipe Two terminations are logical, and the more increase in pipeline gather second as the second end of the heat-transfer pipe and the jet chimney after main pipe Termination is logical.
Preferably, the insulating layer is cylinder-shaped insulating layer, and the insulating layer is spelled by multiple sheet metal heat-insulation units It connects.
Preferably, the jet chimney includes main steam header road and steam branch pipe road, the both ends in the steam branch pipe road It is connected with the main steam header road, the steam isolation is provided on the main steam header road and the steam branch pipe road Valve.
Preferably, the cooling water pipeline includes cooling water main pipeline and cooling water branch pipe(tube), the cooling water branch pipe The both ends in road are connected with the cooling water main pipeline, are provided on the cooling water main pipeline and the cooling water branch pipe(tube) The cooling water isolation valve.
Preferably, the steam drain for discharging water vapour is provided on the cooling water tank.
Preferably, the moisturizing circuit for carrying out moisturizing to the cooling water tank is provided on the cooling water tank.
The invention has the following beneficial effects: system provided by the invention uses passive residual heat removal technology, no Rely on external impetus power supply, so that it may meet the reactor including station blackout and lose under the emergency conditions of normal heat extraction path The demand of Residual heat removal.It is designed using passive two circuit, compared to pool type sodium cooled fast reactor accident afterheat draining technology and European Union Lead cooled fast breeder reactor ALFRED secondary side passive residual heat removal technology, system inner looping is less, and thermal resistance is small, and heat extraction effect is good.Using The outer passive residual heat removal technology of reactor, compared to European Union's Lead cooled fast breeder reactor ALFRED secondary side passive residual heat removal skill Art will not cause thermal shock to steam generator, to reduce its service life, or even cause equipment failure to cause the accident Deterioration, save maintenance cost, improve npp safety.The present invention simplifies design using out-pile, and number of devices is few and nothing Large scale equipment, it is easy for installation, it is easy to maintenance, advantageously reduce reactor vessel inner space, investment reduction cost.Using out-pile Passive residual heat removal technology can be thinned heat transfer tube wall, improve heat transfer efficiency, improve tube wall stress condition, mitigate system weight, Investment reduction cost.The present invention uses out-pile passive residual heat removal technology, conducts heat based on radiation heat transfer, can prevent freezing point There is the phenomenon that local overcooling solidification in higher lead or lead bismuth.
Detailed description of the invention
In order to more clearly explain the embodiment of the invention or the technical proposal in the existing technology, to embodiment or will show below There is attached drawing needed in technical description to be briefly described, it should be apparent that, the accompanying drawings in the following description is only this Some embodiments of invention for those of ordinary skill in the art without creative efforts, can be with It obtains other drawings based on these drawings.
Fig. 1 is the schematic diagram of lead base fast reactor out-pile passive residual heat removal system provided by the invention.
Fig. 2 is the schematic diagram of the increase in pipeline of heat-transfer pipe and decline pipeline in Fig. 1 provided by the invention.
Specific embodiment
The present invention provides a kind of lead base fast reactor out-pile passive residual heat removal system, as shown in Figure 1, the system includes: dress There are cooling water tank 6, jet chimney 5, cooling water pipeline 9, heat-transfer pipe 2, steam isolating 3,4 and the cooling water segregation of cooling water Valve 7,8.
Wherein, the first end of cooling water pipeline 9 and cooling water tank 6 are connected and the first end of cooling water pipeline 9 is located at cooling Below water level, the second end of cooling water pipeline 9 and the first end of heat-transfer pipe 2 are connected.Preferably, the first of cooling water pipeline 9 End and the bottom of cooling water tank 6 are connected.
The first end and cooling water tank 6 of jet chimney 5 are connected, the second end of jet chimney 5 and the second termination of heat-transfer pipe 2 It is logical.
Side on jet chimney 5 close to cooling water tank 6 is provided with steam isolating 3,4, close to cold on cooling water pipeline 9 But the side of water tank 6 is provided with cooling water isolation valve 7,8.
Heat-transfer pipe 2 is U-shaped heat-transfer pipe, and heat-transfer pipe 2 includes increase in pipeline 21 shown in Fig. 2 and connects with increase in pipeline one end The decline pipeline 22 connect is provided with insulating layer 10 between increase in pipeline and the decline pipeline 22.
Heat-transfer pipe 2 is arranged in reactor containment vessel, and the increase in pipeline 21 of heat-transfer pipe 2 is attached to outside reactor vessel 1, Increase in pipeline 21 is used for the heat of absorbing reaction heap primary Ioops.
Preferably, above-mentioned system can also include control device (not shown), and the control device is tight in reactor When emergency stop heap, it can control steam isolating 3,4 and cooling water isolation valve 7,8 automatically turn on.
Further, as shown in Fig. 2, heat-transfer pipe 2 further comprise more increase in pipeline 21 and with more increase in pipeline The 21 more decline pipelines 22 to connect one to one.
More decline pipelines 22, which gather, to be connected after main pipe as the first end of heat-transfer pipe 2 and the second end of cooling water pipeline 9, More increase in pipeline 21, which gather, to be connected after main pipe as the second end of heat-transfer pipe 2 and the second end of jet chimney 5.
Further, insulating layer 10 is cylinder-shaped insulating layer, and insulating layer 10 is spliced by multiple sheet metal heat-insulation units It forms, plays the role of insulation.
Further, jet chimney 5 include main steam header road and steam branch pipe road, the both ends in steam branch pipe road with steaming Vapour main pipeline is connected, and is respectively corresponded on main steam header road and steam branch pipe road and is provided with steam isolating 3,4.
Further, cooling water pipeline 9 include cooling water main pipeline and cooling water branch pipe(tube), the two of cooling water branch pipe(tube) End is connected with cooling water main pipeline, is respectively corresponded on cooling water main pipeline and cooling water branch pipe(tube) and is provided with cooling water isolation valve 7、8。
Further, the steam drain 11 for discharging water vapour is provided on cooling water tank 6.
Further, the moisturizing circuit 12 for carrying out moisturizing to cooling water tank 6 is provided on cooling water tank 6.
Preferably, a penetration piece 13, reactor safety are enclosed in the outside of jet chimney 5 and cooling water pipeline 9 Via hole, jet chimney 5 and cooling water pipeline 9 is provided on shell to extend to inside containment outside containment across the via hole When, the penetration piece 13 for being wrapped in jet chimney 5 is clipped between jet chimney 5 and containment, for protecting jet chimney 5, is wrapped up The penetration piece 13 of cooling water pipeline 9 be clipped between cooling water pipeline 9 and containment, for protecting cooling water pipeline 9.
System provided by the invention can arrange multiple row, can be mutually indepedent between each column.It is lost in nuclear reactor normal Under the accident conditions of heat extraction path, reactor emergency shut-down, can be controlled by control device steam isolating 3,4 and cooling water every It is automatically turned on from valve 7,8, the cooling water in cooling water tank 6 is injected into reaction by jet chimney 5 and cooling water pipeline 9 by gravity In heat-transfer pipe 2 outside heap container 1, cooling water absorbing reaction heap primary Ioops lead or lead bismuth alloy heat in heat-transfer pipe 2 are formed Steam, steam enter 6 lunch of cooling water tank by jet chimney 5 and are condensed into water, form Natural Circulation, realize reactor waste Discharge.When the cooling water in cooling water tank 6 reaches saturation temperature, generated steam is discharged after filtering to atmosphere.With The continuous evaporation of cooling water, when the water level in cooling water tank 6 is lower, can by moisturizing circuit 12 to cooling water tank 6 into Row moisturizing.
Heat-transfer pipe 2 divides for increase in pipeline 21 and declines pipeline 22, and for the realization for guaranteeing Natural Circulation, increase in pipeline 21 is under It drops and is equipped with reactor insulating layer 10 between pipeline 22.
System provided by the invention has the advantages that
The present invention uses passive residual heat removal technology, does not depend on external impetus power supply, so that it may which meeting includes that full factory is disconnected Reactor including electricity loses the demand of Residual heat removal under the emergency conditions of normal heat extraction path.
The present invention is designed using passive two circuit, compared to pool type sodium cooled fast reactor accident afterheat draining technology and European Union's lead Cold fast reactor ALFRED secondary side passive residual heat removal technology, system inner looping is less, and thermal resistance is small, and heat extraction effect is good.
The present invention uses out-pile passive residual heat removal technology, passive compared to European Union's Lead cooled fast breeder reactor ALFRED secondary side Residual heat removal technology will not cause thermal shock to steam generator, to reduce its service life, or even cause equipment failure from And the deterioration to cause the accident, maintenance cost is saved, npp safety is improved.
The present invention simplifies design using out-pile, and number of devices is few and without large scale equipment, easy for installation, easy to maintenance, favorably In reduction 1 inner space of reactor vessel, investment reduction cost.
The present invention uses out-pile passive residual heat removal technology, and 2 wall thickness of heat-transfer pipe can be thinned, and improves heat transfer efficiency, improves Tube wall stress condition mitigates system weight, investment reduction cost.
The present invention uses out-pile passive residual heat removal technology, conducts heat based on radiation heat transfer, freezing point can be prevented higher Lead or lead bismuth there is the phenomenon that local overcooling solidification.
The above content is a further detailed description of the present invention in conjunction with specific preferred embodiments, and it cannot be said that Specific implementation of the invention is only limited to these instructions.For those of ordinary skill in the art to which the present invention belongs, exist Under the premise of not departing from present inventive concept, a number of simple deductions or replacements can also be made, all shall be regarded as belonging to of the invention Protection scope.

Claims (7)

1. a kind of lead base fast reactor out-pile passive residual heat removal system characterized by comprising the cooling water equipped with cooling water Case, jet chimney, cooling water pipeline, heat-transfer pipe, steam isolating, cooling water isolation valve;
Wherein, the first end of the cooling water pipeline is connected with the cooling water tank and the first end of the cooling water pipeline is located at Below cooling water level, the first end of the second end of the cooling water pipeline and the heat-transfer pipe is connected;
The first end of the jet chimney and the cooling water tank are connected, the second end of the jet chimney and the heat-transfer pipe Second end is connected;
Side on the jet chimney close to the cooling water tank is provided with the steam isolating, on the cooling water pipeline Side close to the cooling water tank is provided with the cooling water isolation valve;
The heat-transfer pipe is U-shaped heat-transfer pipe, and the heat-transfer pipe includes increase in pipeline and connect with described increase in pipeline one end Decline pipeline, is provided with insulating layer between the increase in pipeline and the decline pipeline;
The heat-transfer pipe is arranged in reactor containment vessel, and the increase in pipeline of the heat-transfer pipe is attached to outside reactor vessel, The increase in pipeline is used for the heat of absorbing reaction heap primary Ioops.
2. lead base fast reactor out-pile passive residual heat removal system according to claim 1, which is characterized in that the heat-transfer pipe The more decline pipelines for further comprising more increase in pipeline and connecting one to one with the more increase in pipeline;
The more decline pipelines gather the second end after main pipe as the first end of the heat-transfer pipe and the cooling water pipeline It connects, the more increase in pipeline gather the second termination after main pipe as the second end of the heat-transfer pipe and the jet chimney It is logical.
3. lead base fast reactor out-pile passive residual heat removal system according to claim 1, which is characterized in that the insulating layer For cylinder-shaped insulating layer, and the insulating layer is spliced by multiple sheet metal heat-insulation units.
4. lead base fast reactor out-pile passive residual heat removal system according to claim 1, which is characterized in that the steam pipe Road includes main steam header road and steam branch pipe road, and the both ends in the steam branch pipe road are connected with the main steam header road, institute It states and is provided with the steam isolating on main steam header road and the steam branch pipe road.
5. lead base fast reactor out-pile passive residual heat removal system according to claim 1, which is characterized in that the cooling water Pipeline includes cooling water main pipeline and cooling water branch pipe(tube), and the both ends of the cooling water branch pipe(tube) are responsible for the cooling water Road is connected, and is provided with the cooling water isolation valve on the cooling water main pipeline and the cooling water branch pipe(tube).
6. lead base fast reactor out-pile passive residual heat removal system according to claim 1, which is characterized in that the cooling water The steam drain for discharging water vapour is provided on case.
7. lead base fast reactor out-pile passive residual heat removal system according to claim 1, which is characterized in that the cooling water The moisturizing circuit for carrying out moisturizing to the cooling water tank is provided on case.
CN201811557811.6A 2018-12-19 2018-12-19 A kind of lead base fast reactor out-pile passive residual heat removal system Pending CN109545401A (en)

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Cited By (8)

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Publication number Priority date Publication date Assignee Title
CN110580959A (en) * 2019-09-19 2019-12-17 中国原子能科学研究院 Sodium-air heat exchanger
CN111899902A (en) * 2020-09-08 2020-11-06 中国科学院合肥物质科学研究院 Pool type reactor waste heat discharge system controlled by floating ball valve
CN111933315A (en) * 2020-08-11 2020-11-13 中国科学院近代物理研究所 Passive residual heat removal system and method for pool type lead-based reactor
CN112859588A (en) * 2021-01-22 2021-05-28 西安交通大学 Control device and method for rapidly reducing lead bismuth fast reactor waste heat discharge temperature
CN113140337A (en) * 2021-03-05 2021-07-20 国科中子能(青岛)研究院有限公司 Passive cooling system and method for multi-medium shared cooling channel and reactor
CN113450933A (en) * 2021-08-19 2021-09-28 中国原子能科学研究院 Reactor waste heat discharge system and method
CN114743698A (en) * 2022-04-15 2022-07-12 华能核能技术研究院有限公司 Concise waste heat discharge system of high-temperature gas cooled reactor
CN113450933B (en) * 2021-08-19 2024-05-14 中国原子能科学研究院 Reactor waste heat discharging system and method

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Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110580959A (en) * 2019-09-19 2019-12-17 中国原子能科学研究院 Sodium-air heat exchanger
CN111933315A (en) * 2020-08-11 2020-11-13 中国科学院近代物理研究所 Passive residual heat removal system and method for pool type lead-based reactor
CN111899902A (en) * 2020-09-08 2020-11-06 中国科学院合肥物质科学研究院 Pool type reactor waste heat discharge system controlled by floating ball valve
CN112859588A (en) * 2021-01-22 2021-05-28 西安交通大学 Control device and method for rapidly reducing lead bismuth fast reactor waste heat discharge temperature
CN113140337A (en) * 2021-03-05 2021-07-20 国科中子能(青岛)研究院有限公司 Passive cooling system and method for multi-medium shared cooling channel and reactor
CN113140337B (en) * 2021-03-05 2023-09-15 国科中子能(青岛)研究院有限公司 Passive cooling system, method and reactor for multi-medium shared cooling channel
CN113450933A (en) * 2021-08-19 2021-09-28 中国原子能科学研究院 Reactor waste heat discharge system and method
CN113450933B (en) * 2021-08-19 2024-05-14 中国原子能科学研究院 Reactor waste heat discharging system and method
CN114743698A (en) * 2022-04-15 2022-07-12 华能核能技术研究院有限公司 Concise waste heat discharge system of high-temperature gas cooled reactor
CN114743698B (en) * 2022-04-15 2023-06-27 华能核能技术研究院有限公司 Succinct high temperature gas cooled reactor waste heat discharge system

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